主催: 一般社団法人 日本機械学会
会議名: 第21回 動力・エネルギー技術シンポジウム
開催日: 2016/06/16 - 2016/06/17
Removal of molten fuel debris accumulated in Units 1 to 3 of Fukushima Daiichi Nuclear Power Plant must be completed in order to deal start the decommissioning process. Several methods are proposed to remove the fuel debris from PCV/RPV, and it is essential to perform safety assessment for all the possible scenarios. In the present study, numerical model to investigate the three-dimensional distribution of in-vessel heat transfer characteristics of the actual plant condition is developed. The simulation results obtained from the commercial CFD code, STARCCM+, is compared with the actual plant data taken by Tokyo Electric Power Company to verify the validity of the current analysis. Following the confirmation of the model's validity, the numerical analysis was carried out to investigate the expected conditions during “dry method” in 2021, which marks 10 years from the accident.